Overview of the tensile properties of EUROFER in the unirradiated and irradiated conditions

Enrico Lucon, Willy Vandermeulen, Marc Scibetta

    Research outputpeer-review


    On the basis of the results accumulated since the late 90s, several European institutions have recently initiated activities aimed at providing an overview and critical assessment of the mechanical and microstructural properties of EUROFER, the reduced activation ferritic/martensitic steel that is the European candidate structural material for a future fusion reactor. SCK-CEN has been in charge of collecting and analyzing tensile data; the results of our assessment will be presented in this paper, where tensile data have been investigated in relation with various irradiation parameters. Comparisons are also provided with similar data for other RAFM steels, including the Japanese reference RAFM steel F82H-mod.
    Original languageEnglish
    Pages (from-to)254-256
    JournalJournal of Nuclear Materials
    StatePublished - Apr 2009
    EventICFRM13 2007 - 13th International Conference on Fusion Reactor Materials - France - CEA, France, Nice
    Duration: 10 Dec 200714 Dec 2007

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